About this Abstract |
Meeting |
MS&T22: Materials Science & Technology
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Symposium
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Progressive Solutions to Improve Corrosion Resistance of Nuclear Waste Storage Materials
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Presentation Title |
SCC of Nuclear Waste Canisters: Mechanisms and Mitigation |
Author(s) |
Janelle P. Wharry, Haozheng J Qu, Timothy J Montoya, Jason Taylor, Kyle Johnson, Rebecca Schaller, Eric Schindelholz |
On-Site Speaker (Planned) |
Janelle P. Wharry |
Abstract Scope |
This talk aims to understand stress corrosion cracking (SCC) mechanisms and mitigation in nuclear waste storage canisters. In the U.S., more than 86,000 metric tons of nuclear waste are stored in stainless steel canisters within concrete overpacks. Vertical seam welds on canisters may be susceptible to chloride-induced SCC (CISCC). Here, we examine CISCC micromechanisms and explore cold spray as a CISCC mitigation strategy. Coupons of arc welded 304L stainless steel are cold sprayed with 304L, then submerged in boiling MgCl2. In an unsprayed reference, transgranular SCC occurs in the weld heat affected zone; crack propagation is dependent upon Schmid and Taylor factor mismatch. Meanwhile, cold sprayed specimens are resistant to CISCC, although the cold spray layer experiences crevice corrosion. Results are discussed in the context of residual stress, localized strain, and crack tip-dislocation interactions. SNL is managed and operated by NTESS under DOE NNSA contract DE-NA0003525. This document is SAND2022-4685A. |